Probabilistic risk assessment course documentation. Volume 1: PRA fundamentals
The full range of PRA topics is presented, with a special emphasis on systems analysis and PRA applications. Systems analysis topics include system modeling such as fault tree and event tree construction, failure rate data, and human Reliability. The discussion of PRA applications is centered on past and present PRA based programs, such as WASH-1400 and the Interim Reliability Evaluation Program, as well as on some of the potential future applications of PRA. The relationship of PRA to generic safety issues such as station blackout and Anticipated Transient Without Scram (ATWS) is also discussed. In addition to system modeling, the major PRA tasks of accident process analysis, and consequence analysis are presented. An explanation of the results of these activities, and the techniques by which these results are derived, forms the basis for a discussion of these topics. An additional topic which is presented in this course is the topic of PRA management, organization, and evaluation. 84 figs., 41 tabs.
- Research Organization:
- Energy, Inc., Seattle, WA (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6277413
- Report Number(s):
- NUREG/CR-4350/1; SAND-85-1495/1; ON: TI86004393
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ACCIDENTS
C CODES
CALCULATION METHODS
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COMPUTERIZED SIMULATION
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CONTAINMENT SYSTEMS
DOSIMETRY
ENGINEERED SAFETY SYSTEMS
EQUATIONS
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HUMAN FACTORS
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ISOTOPES
MATERIALS
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N CODES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROBABILISTIC ESTIMATION
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SIMULATION
T CODES
THERMAL POWER PLANTS
U CODES
220900* -- Nuclear Reactor Technology-- Reactor Safety
A CODES
ACCIDENTS
C CODES
CALCULATION METHODS
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTAINMENT
CONTAINMENT SYSTEMS
DOSIMETRY
ENGINEERED SAFETY SYSTEMS
EQUATIONS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
HUMAN FACTORS
INTEGRAL EQUATIONS
ISOTOPES
MATERIALS
MATHEMATICAL MODELS
N CODES
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROBABILISTIC ESTIMATION
RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SIMULATION
T CODES
THERMAL POWER PLANTS
U CODES